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Corrosion resistance of 316 stainless steel in a simulated pressurized water reactor improved by laser cladding with chromium 期刊论文
Surface and Coatings Technology, 2022, 卷号: 441
作者:  Gu, Yufen;  Xu, Youwei;  Shi, Yu;  Feng, Changgen;  Volodymyr, Korzhyk
收藏  |  浏览/下载：42/0  |  提交时间：2022/06/20
Optimal Tracking Control for a Discrete Time Nonlinear Nuclear Power System 期刊论文
MATHEMATICAL PROBLEMS IN ENGINEERING, 2022, 卷号: 2022, 页码: 9
作者:  Luan, Zhenhua;  Wang, Mengxuan;  Zhang, Yuzhen;  Wei, Qinglai;  Zhou, Tianmin
收藏  |  浏览/下载：7/0  |  提交时间：2023/02/22
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management 期刊论文
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2022, 卷号: 2022
作者:  Guo, Dingqing;  Wang, Jinkai;  Chen, Chao;  Xia, Dongqin;  Yong, Nuo
收藏  |  浏览/下载：7/0  |  提交时间：2022/12/23
A New Neuro-Optimal Nonlinear Tracking Control Method via Integral Reinforcement Learning with Applications to Nuclear Systems 期刊论文
NEUROCOMPUTING, 2022, 卷号: 483, 页码: 361-369
作者:  Zhong, Weifeng;  Wang, Mengxuan;  Wei, Qinglai;  Lu, Jingwei
收藏  |  浏览/下载：14/0  |  提交时间：2022/06/10
Effect of the frequency on fretting corrosion behavior between Alloy 690TT tube and 405 stainless steel plate in high temperature pressurized water 期刊论文
TRIBOLOGY INTERNATIONAL, 2021, 卷号: 164, 页码: 16
作者:  Zhang, Yusheng;  Ming, Hongliang;  Tang, Lichen;  Wang, Jianqiu;  Qian, Hao
收藏  |  浏览/下载：16/0  |  提交时间：2021/11/22
Environmentally assisted cracking in the fusion boundary region of a SA508-Alloy 52M dissimilar weld joint in simulated primary pressurized water reactor environments 期刊论文
CORROSION SCIENCE, 2021, 卷号: 190, 页码: 13
作者:  Dong, Lijin;  Zhang, Yan;  Han, Yaolei;  Peng, Qunjia;  Han, En-Hou
收藏  |  浏览/下载：21/0  |  提交时间：2021/10/15
A  Nickel  A  Low alloy steel  B  TEM  C  Stress corrosion  C  Corrosion fatigue  C  Welding  
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021) 期刊论文
SCIENTIFIC REPORTS, 2021, 卷号: 11, 期号: 1, 页码: 1
作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou
收藏  |  浏览/下载：2/0  |  提交时间：2021/10/15
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor 期刊论文
SCIENTIFIC REPORTS, 2021, 卷号: 11, 期号: 1, 页码: 9
作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou
收藏  |  浏览/下载：20/0  |  提交时间：2021/10/15
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10
作者:  Tan, Jibo;  Zhang, Ziyu;  Zheng, Hui;  Wang, Xiang;  Gao, Jun
收藏  |  浏览/下载：17/0  |  提交时间：2021/02/02
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10
作者:  Tan, Jibo;  Zhang, Ziyu;  Zheng, Hui;  Wang, Xiang;  Gao, Jun
收藏  |  浏览/下载：15/0  |  提交时间：2021/02/02

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